An experimental program was initiated io determine the extent of fast neutron and gamma ray streaming through the SRL Mark II control and safety rods and to evaluate the adequacy of the shielding provided in these control and safety rods. The methods and procedures used to evaluate these problems are routine and proven for determining gamma-ray and fast neutron dosages using radiation sensitive films and gold foils. The final experimental results indicated that no excessive streaming of either gamma rays or fast neutrons is present above or around the SHE Mark II control and safety rods. The analytical attenuation methods used to calculate the fast neutron and gamma-ray streaming dose rates gave results that compared favorably with the experimental data. Even ihough the agreement was favorable, it cannot be concluded that these analyical methods would be equally valid for other annular geometries. Additional experimental work will be necessary in order to establish the validity for performing similar analysis, but the favorable agreement encourages the use of such methods until other methods are determined. (auth)

The casting of shapes of uranium--molybdenum metal of varying sizes and thicknesses from a molten charge has been successfally accomplished with specificially designed graphite distributors and molds. Solid cylinders, hollow cylinders, and flat plate shapes were cast in gang molds. As many as 35 solid cylinders have been cast simultaneously. All castings had smooth surfaces, and solid shapes were cast to 0.006-in. tolerance on all dimensions except length. (auth)

An analysis was made of the fission-gas-release incident during the pressure pumpdown of the AE-6 Reactor resulting in the contamination of the reactor room and members of the operating staff. Descriptions are given of the normal core pumping procedures, procedural alterations during the incident, the discovery of the contamination and its possible causes, and the remedial actions taken. Steps taken to minimize the chance of the occurrence of the contamination in the future are listed. (B.O.G.)

In the reaction of silicon halides with graphite to form silicon carbide, thermodynamic conditions were determined for the formation of SiC, free of elemental silicon. The use of these conditions was designed to limit the rate of coating formation by the rate of diffusion of carbon through the coating, and render the operation independent of the vapor-flow factors which normally limit the uniformity of vapor-deposited coatings. Although a wide range of pressure- temperaturecomposition conditions was explored, it was not possible to duplicate the success previously obtained in applying the method to NbC, TaC, TiC, and ZrC coatings. Fundamental differences in the characteristics of the carbides which may account for the difference in behavior are the lack of a range of homogeneity in beta SiC crystal structure, and the fact that SiC undergoes a modification from the cubic beta to a hexagonal form at l900 to 2000 deg C.There remains the prospect of forming a uniform SiC ''sponge'' by the present process which can be subsequently impregnated with metallic silicon to form an oxidation-resistant cpating. (auth) l6200 Preliminary results were obtained on the value that commercially pure Pu (95% Pu/sub 235/ and 5% Pu/subp 240/) has when used as nuclear fuel. …

The Facilities Engineering Operation of the Chemical Processing Department prepared a process study scope design of a large thermal diffusion plant for xenon isotope separation. This scoping was done perforce on the basis of calculations made from exclusively theoretical considerations because actual design data are not available. The designers are of the opinion, however, that, such a basis is not adequate to justify the construction of the plant and have, therefore, requested that an appropriate supporting research and development program be carried out. This report presents an experimental plan for obtaining the data required. Anticipated results from the proposed experiments as outlined below, are expected to be useful for determining the correlation of thermal diffusion column theory with practice for this particular system of xenon isotopes. An interpretation of the data will permit the determination of the sensitivity of the column parameters to the change in operational and design variables over which the designer and operator have control. Basic observations made on the behavior of xenon may, in addition, be of general scientific and technological interest. Included in the report are estimates of the kind and quantity of data to be obtained, the analytical services required, and the total analytical …

This paper presents a scope design of two coaxial type thermal diffusion columns. These experimental columns are proposed to meet the requirements of the research and development program given in Part 2 of this report series. They would rearrange the isotopes of xenon from the Case II product of the Purex Gas Separations Facility to yield a product with a composite neutron absorption cross section of less than one barn. The theoretical basis for the design is given in Part 1. The auxiliary equipment necessary for the operation and control of the columns is described in Part 4. Major components of the columns and their functions are described in this part, The proposals for the materials of construction and the heating systems are not conclusive. Several possibilities for these requirements, however, are included. The design of two experimental thermal diffusion columns is given to meet the needs of a proposed research and development program for rearranging the isotopes of xenon. The proposed columns are six meters in length and have a maximum diameter of about five inches. They could be built at Hanford for an estimated cost of $10,000.

Atomic Energy Commission has expressed interest in obtaining xenon with a composite neutron absorption cross section of less than one barn. This material may be obtainable from the off-gas of the Purex dissolver. A proposed gas purification facility would process the Purex off-gas through two distillation steps for isolation of a ``rough`` cut of xenon isotopes containing principally Xe{sup 131}, Xe{sup 132}, Xe{sup 134}, Xe{sup 136}, and a small quantity of krypton. This material would become the feed stream for a thermal diffusion plant for xenon isotope separation. Thermal diffusion has been shown to be the most economical way to concentrate the two heavier xenon isotopes of low cross section and to reject the krypton along with lighter xenon isotopes of high cross section. The objective of the work herein reported was to provide the basis for (l) a scope design of pilot thermal diffusion equipment and (2) design of experiments to be made with this equipment. In the absence of experimental data, the pilot design was developed from theoretical considerations of the parameters considered important in thermal diffusion column operations. It was assumed that the pilot unit would have to provide information on the correlation of theory with practice …

Knowledge has developed steadily over the past 18 months toward defining the characteristics of the gamma and neutron radiation associated with plutonium and its compounds. Laboratory measurement have been made on plutonium samples taken from the RMA Line, film badge studies have been made in plutonium processing areas, and calculations have been made predicting dose rates and shielding requirements at higher plutonium exposure levels. As these studies continue, and more precise data is accumulated, it will be possible to (1) more accurately evaluate the radiation received by operating personnel, and (2) more accurately (and economically) specify shielding for facilities designed for processing high exposure plutonium. This report gives the results of a gamma energy analysis of the RMA Line and Recuplex obtained with a laboratory model gamma spectrometer. Measurements have been made in the 234-5 Building which have defined the general gamma energy spectrum emitted by the plutonium processing hoods on the RMA Line and in Recuplex. The data obtained from this study has helped resolve the discrepancy between laboratory data and film badge data, and has provided additional information to help in prediction of the gamma radiation levels to be expected from plutonium irradiated to 2000 MWD/T (NPR) and …

It is deemed feasible to store reactor fuel wastes in a salt dome cavity to a depth where the differential in pressure between the soil over-burden pressure and pressure of the fluid inside the cavity does not exceed 3000 psi, and the temperature is less than 400 deg F. Tests at pressure increments of 1000 psi were conducted on a 2" cylindrical cavity contained in a 6-in. long by 6-in. cylindrical salt core. Tests indicate that the cavity exhibited complete stability under pressures to 3000 psi and temperatures to 300 deg F. At temperatures of 100 to 400 deg F and pressures to 5000 psi continuous deformation of the cavity resulted. Initial movement of the salt was observed at all pressures. This was evidenced by vertical deformation and cavity size reduction. It was noted that a point of structural equilibrium was reached at lower temperatures when the pressure did not exceed 5000 psi. A literature study reveals that the most common type of cavity utilized in liquefied petroleum gas storage is either cylindrical or ellipsoidal. A few are pear or inverted cone shaped. There was no indication of leakage for cavities when pressure tested for as long as 72 hr. …

Weight increases during the oxidation of irradiated foils of pure copper were greater than for unirraaiated specimens. Enhanced reactivity appeared to be strongest in the thin-film region up to about 5 mu g/cm/sub 2/. Oxide film (Cu/ sub 2/O) thickness for both irradiated and unirradiated specimens was approximately 1200 A. Radiation did not affect the reduction of Cu/sub 2/O during the induction period (period in which the reduction proceeds very slowly or not at all). In later stages of the reduction process, a serious lack of reproducibility was observed. Radiation effects on films of Cu/sub 2/O formed by prior oxidation of the copper substrate decreased the kinetics of secondary oxidation. The secondary oxidation curve exhibited a large gap at the point of interrnption for irradiation. The development of an automatic recording microbalance of high sensitivity and a furnace for studies in reactor radiation fields is reported. Measurements were made of the electrode potentials of irradiated (5.5 x 10/sup 19/ neutrons cm/sup -2/) copper, aluminum, magnesium, and zirconium. Cell potentials were found to be dominated by the oxide films formed on the electrode surfaces. The results indicate that radiation does affect the local anode reaction potential. No significant difference between the …

This document has been written in part to answer questions concerning the feasibility and advisability of ``quickie`` discharge of ruptures at C Reactor. Justification of full pile operational charge-discharge (OC-D) is based in part on outage savings resulting from improved, rupture removal. Since a portion of the rupture removals might be accomplished within the scram recovery time (quickie) it is necessary to consider recovery time as a function of anticipated future power levels. In addition to answering the questions mentioned above, it was felt worthwhile at this time to discuss equilibrium control problems associated with OC-D which have been apparent during operation of prototype equipment, and on the basis of this information to consider reactor control with full pile OC-D.

Early work on the antiproton, particularly that part which led to the first paper on the subject, is described. Conclusions that can be drawn purely from the existence of the antiproton are discussed. (W.D.M.)

Solid phases in the zirconium-nitric acid-hydrofluoric acid system were identified by chemical and x-ray diffraction methods. Five different compounds were crystallized at various temperatures and fluoride concentrations from fluoride or fluoborate solutions. These include the mono- and trihydrates of zirconium tetrafluoride, plus three hydrolysis products which possess a fluoride- to-zirconium ratio of approximately three, yet produce different x-ray patterns. The trifluorides crystallize from solutions of low fluoride-to-zirconium ratio at temperatures of below 90, 65 to 100, and above above 95 deg C, respectively. Solubilities of these basic trifluorides were measured at 25 deg C in 1, 6, and 16M nitric acid. (auth)

The effect of fuel programming, i.e., the scheme used for changing fuel in a core, on the reactivity and specific power of a sodium graphite reactor is discussed Fuel programs considered Include replacing fuel a core-load at a time or a radial zone at a time, replacing fuel to manutain the same average exposure of fuel elements throughout the core, and replacing and transferring fuel elements to maintain more highly exposed fuel in the center or at the periphery of the core. Flux and criticality calculations show the degree of power flattening and the concurrent decrease in effective multiplication which results from maintaining more exposed fuel toward the core center. Corverse effects are shown for the case of maintaining more exposed fuel near the core periphery. The excess reactivity which must be controlled in the various programs is considered. Illustrative schedules for implementing each of these programs in an SGR are presented. (auth)

The general prospects of several radioisotopes are reviewed; the special properties of U/sup 232/ and Th/sup 228/ are poi nted out; and ionium (Th/sup 230/ ) and protactinium target materials are discussed from the sthndpoint of availability and chemical separations processes required for the preparation of U/ sup 232/ and Th/sup 228/. Outlines are given for potential schem es for the separation of U/sup 232/ and Th/sup 228/ from uranium milling pr ocess waste streams and from the irradiation products of Th/sup 230/--Th/sup 232/ mixtures. The high heat generating rates of these potent alpha emitters make them especially suitable for primary consideration as heat sources for small thermoelectric generators. The exceptionally high alpha activity suggests their use in special neutron sources as Ra-Be sources, and they may have sufficiently high neutron generating rates to be in contention with some of the smaller research reactors and experimental neutron producers. (B.O.G.)

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Two designs of sodium cold traps for the HNPF have been subjected to full scale tests, Performance features that were investigated include oxide removal efficiency, oxide capacity, pressure drop characteristics, economizer effectiveness, and temperature profiles, Results indicate that both designs should perform satisfactorily in the Hallam plant, (auth)

The ''absolute'' containment of ions in the DCX magnetic mirror field resulting from the cylindrical symmetry of the field is discussed. The regions of confine;, ment in space and momentum are plotted for 300-kev deuterons. (auth)

Electrical resistivity data for metals which are likely to be resistance heated in heat-transfer tests were compiled and are given as a function of temperature. (auth)

Physics scoping studies of a 300-Mw(e) PuO/sub 2/-UO/sub 2/-fueled fast- breeder reactor are reported. Physics design parameters that effect fuel costs, full conservation, and reactor safety were evaluated for use in the selection of parameters for a reference design. The total breeding ratio varied from 1.1 to 1.5 in the range of parameters corsidered. Plutonium core loading ranged from 500 to 1500 kg. Doubling time was found to be reduced by high-density fuel and low steel content. A compromise figure on fuel-rod range of sizes (about 100 mils) yields a 5 operating reactivity and a small, negative sodium temperature coefficient. (J.R.D.)

The prompt neutron lifetime of the SRE was measured by both the oscillation and random noise techniques. Measurement by use of the oscillation technique gave a prompt neutron lifetime of (5 25 plus or minus 0 35) x 10/sup - 4/ sec for a calculated beta of 7 x 10/sup -3/. The measured noise response indicated a lifetime of (5.25 plus or minus 0.7) x 10/sup -4/ sec. Both measured values are in agreement with the calculated value of 5 x 10/sup -4/ sec. Four experiments utilizing the noise analysis technique were performed to determine the prompt neutron lifetime of the KEWB. All four experiments gave results which agreed within 3%, For an estimated beta of 8 x 10/sup -3/, the measured value obtained was (7.8 plus or minus 0.3) x 10/sup -5/ sec. This is in reasonable agreement with both the energy independert calculated value of 6.6 x 10/sup -5/ see and the value of 6.2 x 10/sup -5/ sec obtained from the experimental inhour equation The oscillation technique has been found to be better suited for lifetime determinations in reactors where the prompt neutron break frequency is less than 5 cps. Reactor noise analysis is more suitable for …

The thermal expansions of commercial uranium dioxide specimens were measured up to the melting point. The linear expansion of dense, normal grain size UO/sub 2/ follows closely the equationi L = L/sub 0/(1 + 6.0 x 10/sup -6/t + 2.0 x 10/sup -9/t/sup 1.7 x 10/sup -12/t/sup 3/). An anomalous expansion was noted in the temperature range 1000 to 1500 deg C. Above 2500 deg C the rapid vaporization and crystal growth of UO/sub 2/ necessitate the application of heating techniques which provide rapid heating and quenching in order to obtain reliable data. The use of solar and arcmelting furnaces for this type of measurement is described. (auth)

This is the monthly report for the Hanford Laboratories Operation, February, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection operation, and laboratories auxiliaries operation area discussed.

This is the monthly report for the Hanford Laboratories Operation, May, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, and laboratory auxiliaries operation area discussed.